ML20093H357

Monthly Operating Rept for Sept 1995 for Oyster Creek Nuclear Generating Station

ML20093H357
Person / Time
Site:	Oyster Creek
Issue date:	09/30/1995
From:	J. J. Barton, Edelmann P GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-95-2308, NUDOCS 9510200109
Download: ML20093H357 (7)

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GPU Nuclear Corporation e Nuclear  ::'en:r388 Forked River, New Jersey 087310388 609 971-4000 Writer's Direct Dial Number:

October 11, 1995 C321-95-2308 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report - September,1995 in accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1.C, enclosed are two (2) copies of the Monthly Operating Data (gray book information) for the Oyster Creek Nuclear Generating Station.

If you should have any questions, please contact Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.

M incere ry '

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/ Jo n J. gl dent and Direc V e Presi ton ster Creek

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JJB/BDEM:gl Attachment ec: Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager rc n.

AvUUQy 9510200109 950930 PDR ADOCK 05000219 R PDR f 7 GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation I l L.

SUMMARY

September,1995 Oyster Creek operated the entire month at full power. During the month, the plant generated 447,572 net MWH electric and attained a MDC net capacity factor of 100.4%.

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Oyster Creek Station #1 i Docket No. 50 219 REFUELING INFORMATION SEPTBMBER,1995 l

! Name of Facility: Dyster Creek Station #1 i Scheduled date for next refueling shutdown:

. September,1996

! Scheduled date for restart following refueling: Currently projected for November,1996 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

f No j Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design

or perforn.ance analysis methods. 3 3nificant changes in fust design, new operating procedures

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1. General Electric Fuel Assemblies Fuel design and performance analysis methods have been approved by the NRC.

f The number of fuel assemblies (a) in the core - 580

. (b) in the spent fuel storage pool - 2048 (c)in dry storage - 24 The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been

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j requested or is planned, in number of fuel assemblies:

4 Present Licensed Capacity: 2545 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Full core discharge capacity to the spent fuel pool will be available through the 1996 refueling outage.

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AVERAGE DAILY POWER LEVEL NET MWe j

l DOCKET #. . . . . . . . . . . 50 219 UNIT. . . . . . . . 0YSTER CREEK #1 REPORT DATE. . . . . . . .1018I95 COMPILED BY . . . . . . . . PAUL EDELM ANN TELEPHONE # . . . . . . 809 9714097 MONTH: SEPTEMBER,1995 E MW W ME

] 1. 815 18. 821 j 2. 815 17. 822

3. 817 18. 828

4. 818 19, 825 i

5. 818 20. 828

$ 8. 817 21. 824 i

7. 814 22. 820 i 8. 812 23. 825

9. 815 24. 829

, 10. 819 25. 828

11. 822 28. 831

12. 822 27. 829 l

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13. 818 28. 830 l I

14. 817 29. 830

15. 819 30. 831 i

(p:Wes-95\$414 95\opdata.cor\ report:28)

i t- , OPERATING DATA REPORT

. OPERATING STATUS

1. D0CNET: 50 219

2. ' REPORTING PERIOD: Sep85

3. UTILITY CONTACT: PAUL EDELMANN (809 9714097) i

4. LICENSED THERMAL POWER IMWth 1930

5. - NAMEPLATE RATING (GR088 MWe): 887.5 x 0.8 - 550

8. DESIGN ELECTRICAL RATING (NET MWe)

850

7. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe)

841 5 8. MAXIMUM DEPENDABLE CAPACITY (NET MWe): 819

9. IF CHANGES OCCUR AB0VE SINCE LAST REPORT, GIVE REASONS:

l NONE

< 10. POWER LEVEL TO WHICH RESTRICTED,IF ANY (NET MWe):

NONE

11. REASON FOR RESTRICTION,IF ANY:

. NONE MONTH YEAR CUMULATIVE

12. REPORT PERIOD HOURS 720.0 8551.0 225911.0

13. HOURS RX CRITICAL 720.0 8551.0 152351.7 l

14. RX RESERVE SHUT 00WN HR8 0.0 0.0 918.2 l

15. HR$ GENERATOR ON LINE 720.0 8551.0 148850.1 i 18. UT RE8ERVE SHTDWN HR8 0.0 0.0 0.0 4

17. GROSS THERM ENERGY (MWH) 1388117 12305001 258828705 4 18. GROSS ELEC ENERGY (MWH) 484522 4139219 88185510

19. NET ELEC ENERGY (MWH) 447572 3989478 82884583

, 20. UT SERVICE FACTOR 100.0 100.0 85.9

21. UT AVAIL FACTOR 100.0 100.0 85.9

22. UT CAP FACTOR (MDC NET) 100.4 98.4 59.7

23. UT CAP FACTOR (DER NET) 95.8 93.7 58.3

24. UT FORCED OUTAGE RATE 0.0 0.0 9.9

, 25. FORCED OUTAGE HR8 0.0 0.0 18289.8

28. SHUTDOWNS SCHEDULE 0 OVER NEXT 8 MONTHS (TYPE, DATE, DURATION):

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NONE

, 27. IF CURRENTLY SHUTD0WN, ESTIMATED STARTUP DATE: N/A (pMocs-95\5414 95\opdata.cor\ report 29)

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MONTHLY OPERATING REPORT LICENSEE EVENT REPORTS The following Licensee Event Reports were submitted during the month of September,1995:

LER 95-005: Anticipatory Scram Bypass Switches' Non-Conservative Setpoint Due to Original Plant Design Turing a review of General Electric SIL 423 a non-conservative instrument setpoint for the anticipatory scram bypass pressure switches was identified.

The design deficiency of this non-conservative setpoint had existed since the ,

I incorporation of the anticipatory scrams early in plant operation. This condition indicates that the turbine stop valve closure and turbine control valve fast closure scrams were still bypassed above 40% reactor thermal power, at worst case up to approximately 49% reactor thermal power, during plant i power ascensions and reductions. The safety significance of the non- l conservative setpoint is considered minimal. Subsequent analyses have shown that a bypass of these scrams at 50% reactor thermal power would not exceed fuel cladding integrity safety limits. The setpoint of the pressure switches was lowered to a conservative value with respect to 40% reactor thermal power.

A comprehensive analysis of the instrument characteristics based upon historical data is being performed. The results will be incorporated into the existing setpoint determination and any necessary changes will be made. The plant operating procedures are being revised to provide clarification and improve awareness of plant manipulations which could impact this automatic bypass feature. Possible modifications to these features will be considered, i

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UNIT SHUTDOWN AND POWER REDUCTIONS '.

DOCKET NO.: 50-219 UNIT NAME: Oyster Creek DATE: October 09.1995 i COMPLETED BY: David M. Eran TELEPHONE: 971 4818 REPORT MONTH: SEPTEMBER 1995 TYPE METHOD OF SHUTTING CORRECTIVE DATE NO. F: Forced DURATION REASON (1) DOWN THE REACTOR OR ACTIONS / COMMENTS S: Scheduled (Hours) REDUCING PORTR (2)

There were no shutdown or significant power reductions during this reporting period l

i Sununary:

(1) Reason (2) METHOD i

a. Equipment Failure (Explain) e. Operator Training & Lic. Exam 1. Manual

b. Maintenance or Test f. Administrative 2. Manual Scram  !

c. Refueling g. Operational Error (Explain) 3. Automatic Scram

d. Regulatory Restriction h. Other (Explain) 4. Other (Explain) l f

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